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A control method for the main steam bypass system of a pressurized water reactor nuclear power unit

A technology of bypass system and nuclear power unit, applied in the direction of design optimization/simulation, etc., can solve the problems of energy carry-out that cannot guarantee the energy exchange of steam generators, high temperature damage of steam generators and reactors, severe nuclear power accidents, etc., to achieve effective It is beneficial to control, prevent large fluctuations, and improve the effect of opening range

Active Publication Date: 2022-04-22
ELECTRIC POWER RES INST OF GUANGXI POWER GRID CO LTD
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Problems solved by technology

When the main steam bypass system is improper, it will not be possible to ensure that the steam generator will take out the energy exchanged between the primary circuit and the secondary circuit, resulting in high temperature damage to the steam generator and reactor, which will lead to serious nuclear power accidents and even nuclear leakage accidents
At present, there is no scientific control method for the main steam bypass system

Method used

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  • A control method for the main steam bypass system of a pressurized water reactor nuclear power unit
  • A control method for the main steam bypass system of a pressurized water reactor nuclear power unit
  • A control method for the main steam bypass system of a pressurized water reactor nuclear power unit

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Embodiment Construction

[0022] In order to better understand the present invention, the present invention will be further described below in conjunction with accompanying drawing and specific embodiment:

[0023] Such as figure 1 As shown, the main steam bypass system is led out from the main steam pipe of the secondary circuit, and the leading position is the main steam outlet main pipe of the secondary circuit of the steam generator, which is located in front of the high-pressure regulating valve of the steam turbine, and passes through the bypass valve or between the leading outlet and the condenser. The bypass valve group is connected by metal pipes; figure 2 As shown, a control method for the main steam bypass system of a pressurized water reactor nuclear power unit comprises the following steps:

[0024] S1: Use the A / D conversion module I1 to convert the power signal P output by the generator into a digital signal. When the power signal P of the generator is digitized, it will be processed i...

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Abstract

The invention relates to the technical field of nuclear power unit control, in particular to a control method for a main steam bypass system of a pressurized water reactor nuclear power unit. Aiming at the drastic changes in operating conditions such as load shedding and power consumption of the unit, or steam turbine idling after load shedding, a control method for the main steam bypass system of the pressurized water reactor nuclear power unit is proposed for the bypass system of the nuclear power unit. To make the unit fast and stable, to realize load shedding and island operation with factory power or smooth shutdown, the present invention uses the multiplication result of the output values ​​of the threshold control module and the temperature control module as the opening instruction for controlling the bypass valve. The frequent opening and closing of the bypass valve is avoided. At the same time, when the output difference between the A / D conversion module II and the power control module is too large, the output value of the threshold control module increases in steps to improve the bypass valve. The opening range is conducive to the control of the main steam pressure of the secondary circuit and prevents large fluctuations.

Description

technical field [0001] The invention relates to the technical field of nuclear power unit control, in particular to a control method for a main steam bypass system of a pressurized water reactor nuclear power unit. Background technique [0002] The main steam bypass system of the pressurized water reactor nuclear power unit is an important protection device to prevent the steam pressure of the secondary circuit from exceeding the standard, and to prevent the safe operation of the steam generator and the reactor connected to it. The U-shaped metal tube of the steam generator of the pressurized water reactor nuclear power unit transfers the heat of the high-temperature and high-pressure coolant coming out of the reactor to the feed water of the secondary circuit. After absorbing the heat, the feed water of the secondary circuit undergoes phase transformation into steam to drive the steam turbine. When the power of the generator does not match the power of the reactor, especial...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G06F30/20
Inventor 文立斌刘光时雷亭吴健旭
Owner ELECTRIC POWER RES INST OF GUANGXI POWER GRID CO LTD
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